ML20114C645
| ML20114C645 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 08/25/1992 |
| From: | Shiraki C Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20114C647 | List: |
| References | |
| NUDOCS 9209030040 | |
| Download: ML20114C645 (5) | |
Text
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UNITED STATES
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E NUCLEAR REGULATORY COMMISSION
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IOWA ELECTRIC LIGHT AND POWER COMPANY CENTRAL 10WA POWER COOPERATIVE CORN BELT POWER COOPERATIVF DOCKET NO. 50-331 DUANE ARNOLD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. )87 License No. OPR-49 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment tj lowa Electric Light and Power Company, et al., dated February 18, 1992, complies with the st<1dards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of ti Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations:
D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all apnlicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operatina License No. OPR-49 is hereby amended to read as follows:
9209030040 920025 ADOCK 0S00 1
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(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.187. are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of the date of issuance and sha_ll be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/S #'A.
Clyde Y. Shiraki, Sr "r0 Ject Manager Project Directorate I' 3
Division of Reactor Projects Ill/IV/V Office of Nuclear Raactor Regulation
Attachment:
Changes to the Technical Specificatior.s Date of issuance:. August 25, 1992 y..
ATTACHMENT TO LICENSE AMENDMENT NO.187__
[A(_lLJTY OPERATING LICENSE NO. DPR-49 tiOCKET tl3. 50-331 Replace the following page of the Appendix A Technical Specifications with the enclosed page. The revised. areas are indicated by marginal lines.
Reicove Insert 3.2-13 3.2-13 3.2 -3.2-40 W,
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4' TABLE'3.2-B (Continued)
INSTRUMENTATION THAT INITIATES OR CONTROLS THE CORE 2
AND CONTAINMENT COOLING SYSTEMS.
!E-Hinimum No.
of Opere.bic g
Instrument Number of d)
Channels Per Instrument Channels S
Trip System (1)
Trip' Function Trip Level Setting Provided by Design Remarks c5 2
Suppression Chamber s 5" above normal 2 Instrument Channels Transfers HPCI pump I
HPCI Suction Level.
water level taction to' suppression
{$
chamber H
1 RCIC Turbine High 5 155 Inches H,4h3
- 2. Instrument Channels
[
Flow 2
RCIC Turbine 5 175'F 4 Instrument Channels o
Egyipment Room-High Ambient
- g3 Temperature 73 2
RCIC Vent High s A 50*F,
4 Instrument Channels e
{'
Differential Tamperature 2
RCIC Steam Line 100 > P > 50 psigo 4 Instrument Channels
-I Low Pressure s
1 HPCI Turbine Steam s 103 Inches Hfh3; 2 Instrument Channels Line High Flow (Outboard Instr.)
5 386 Inches Hpo, (Inboard Instr.)
2 Suppressicn Pool Area 150*F 4 Instrument Channels High inblent Temperatere 2
Suppression Pool Area
'50*F 4 Instrument Channels High Differential Temperature 1
HPCI Leak Detection 15 min.
2 Instrument Channels Time Delay l
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t DAEC-1 The HPCI high flow and temperature instrumention are provided to detect a break in the HPCI steam piping. Tripping of this instrumentation results in actuation of i
HPCI-isolation valves. Tripping logic for the high flow is a 1 out of 2 logic.
i Temperature is monitored at two (2) locations with four (4) temperature sensors at each location.
Two (2) sensors at each location are powered by "A" direct current control bus and two (2) by "B" direct current control bus.
Esch pair of sensors, e.g.,
"A" or "B",
at each location are physically esparated and the tripping of either "A" or."B" bus sensor will actuate HPCI isolation valvec.
The trip settings of 103 inches H0 (outboard instrument) and 386 inches H:0 (inboard l instrument) which correspond to 300% of design flow for high flow and 175'T and A45' l for high temperature are such that core uncovery is prevented and fission product release is within limits.
The RCIC high flow and temperature instrumentation are arranged the same as that for the HPCI.
The trip setting of 155 inches H:0 for high flow and 175* and A45' for l
temperature are based on the same criteria as the HPCI.
i-i' i
l Amendment No. 26,187 3.2-40 i
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